ML20247J773

Special Rept:On 890815,dampers Failed to Comply W/Ul Requirements of Std 555-1968.Caused by Improper Fabrication. All Applicable Fire Dampers in Affected Areas W/Combustible Loading Exceeding 1 H Per 10CFR50,App R Will Be Replaced

ML20247J773
Person / Time
Site:	Beaver Valley
Issue date:	09/15/1989
From:	Noonan T DUQUESNE LIGHT CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
GL-88-12, ND3MNO:1953, TAC-56566, NUDOCS 8909200280
Download: ML20247J773 (5)

Text

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A YA>N M Telephone (412) 393-6000 Nuclear Group P O Bon d Sept. 15, 1989 ,

snippinoport PA 1s0774004 NMMO

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Beaver Valley Power Station, Unit No. 1 Docket No. 50-334, License No. DPR-66 Special Report U. S. Nuclear Regulatory' Commission Attn: Document Control Desk washington, DC 20555

Reference:

TAC 56566 Gentlemen:

In accordance with the guidance provided in NRC Generic Letter 88-12, the Fire Protection Technical Specifications for Beaver Valley Unit 1 were incorporated into the Station's Updated Final Safety Analysis Report (UFSAR) and Station Administrative Procedures (SAP),

as approved in TS Amendment 136. . As such, the operational conditions, remedial actions, and requirements associated with the removed Fire Protection TS have been incorporated into SAP 9D " Fire Protection".

Therefore, the following Special Report is being submitted for inoperable fire rated assemblies, to outline the cause of the inoperability, the actions taken to mitigate the effects of the problem, and the plans for restoring the system to operable status.

On August 15, 1989 the Nuclear Engineering Department received a report from Underwriter's Laboratories (UL) , File NC1105/ Project 89NK10962, regarding the results of the fire testing for vertically mounted prototype fire dampers applicable to BVPS-1 conducted on August 7 and 8, 1989. The test results indicated that the dampers failed to comply with the requirements of Standard 555-1968.

The applicable dampers installed at BVPS-1 in configurations correlating to those of the tested prototypes are:

A 8909200280 890915 PDR ADOCK 05000334  : g g PDC

4 S2pt. 15, 1989 i

.', ND3MNO 1953

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' Fire Dampers Locations Affected VS-D-263 & 266 East and West Emergency Switchgear Rooms VS-D-160, 161 & 177 East and West Cable Vaults VS-D-162, 163, 165 thru 167 Main Steam Valve Area VS-D-269, 284 & 285 Cable Tray Mezzanine and Normal Switchgear Room VS-D-170 thru 176, & 178 Primary Auxiliary Bldg.

(El. 768) and Steam Generator Blowdown Room VS-D-188 thru 191 Primary Auxiliary Bldg.

(El. 768) and Fuel Bldg.

VS-D-194 Primary Auxiliary Bldg.

(El. 752) and Service Bldg.

The above listed dampers were declared inoperable on that same day. In addition, hourly patrols and continuous fire watches were posted in the affected areas, in accordance with SAP 9D " Fire Protection" requirements. Furthermore, an analysis was conducted to determine compliance with safe shutdown capability as outlined in 10 CFR 50 7ppendix R. This analysis also considered the applicability of reporting requirements under 10 CFR 50.72 and 10 CFR 50.73.

It was concluded that the lack of proper qualification for the vertical fire dampers did not compromise more than one train of equipment required for the safe shutdown of BVPS-1 and therefore was not an unanalyzed condition reportable under 10 CFR 50.72.b.1.ii.A.

or 10 CFR 50.73.a.2.ii.A.

The cause of the damper's failure to comply with the UL Standard 555 test and their resultant inoperability, was improper fabrication. The dampers were field-fabH eated by Schneider Sheet Metal, who did not obtain UL fire rating labels for them; although the dampers were to have been manufactured in accordance with UL-approved SMACNA (Sheet Metal and Air Conditioning Contractors National Association) specifications. In actuality, various inconsistencies between the SMACNA design and that of the installed dampers contributed to their failure when they were finally tested (by a 90 minute fire endurance and a hose stream test) for UL qualification.

Srpt. 15, 1989

' , . .ND3MNO:1953 Page Three f

.The. hourly roving and continuous fire watches will remain in-effect until corrective actions are completed or . analyses are performed to support the present configurations. Currently the plans  ;

are to replace all applicable . fire dampers in affected areas with combustible loadings exceeding i hour as indicated in the 10 CFR 50 Appendix R Fire Hazards Analysis. For areas that do not exceed 1 l hour combustible ~ loading, an evaluation is being conducted on a case-by-case. basis, to determine the acceptability of the existing.  ;

sheet metal ductwork. This acceptability is based on National Fire  !

Protection Association (NFPA) Codt 90A and UL Standard 263 " Fire Tests of. Building- Construction. and Materials," which indicate that L eel ductwork .022 inches thick (24 gauge) can withstand a fire for'  ;

1 ' hour. This methodology was recently approved at another facility j by the- NRC. The analysis is being conducted in accordance with the l guidance provided in'NRC Generic Letter 86-10, regarding unqualified, i untested configurations.

If there are any questions regarding this matter, please contact my staff. .

T. P. Noonan  !

Plant Manager i

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b::pt. 15, 1989

, ND3MNO:3953 Page Four cc: Mr. William T. Russell Regional Administrator United States Nuclear Regulatory Commission Region 1 King of Prussia, PA 19406 C. A. Roteck, Ohio Edison Mr. Peter Tam, BVPS Licensing Project Manager United States Nuclear. Regulatory Commission Washington, DC 20555 J. Beall, Nuc], tar Regulatory Commission, BVPS Senior Resident Inspector Mr. Alex Timme, CAPCO Nuclear l Projects Coordinator Toledo Edison INPO Records Center Suite 1500 1100 Circle 75 Parkway Atlanta, GA 30339 G. E. Muckle, Factory Mutual Engineering, Pittsburgh Mr. J. N. Steinmetz, Operating Plant Pr3jects Manager Mid Atlantic Aret Westinghouse Electric Corporation Energy Systems Service Division Box'355 Pittsburgh, PA 15230 American Nuclear Insurers c/o Dottie Sherman, ANI Library The Exchange Suite 245 270 Farmington Avenue Farmington, CT 06032 l

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